58-Ce-137MJAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 5829 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-10 Evaluated with CCONE code by N.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only AP is assumed to be 7.14 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.40191E+01 Elastic 6.43187E+00 Inelas 1.26396E-02 1.08160E+00 n,gamma 7.40373E+00 6.14326E+02 n,p 5.28674E-06 4.39356E-04 n,alpha 1.13683E-06 9.66217E-05 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /1/. MT= 2 Elastic scattering cross section Calculated with CCONE code /1/. MT= 4,51-91 (n,n') cross section Calculated with CCONE code /1/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /1/. MT= 16 (n,2n) cross section Calculated with CCONE code /1/. MT= 17 (n,3n) cross section Calculated with CCONE code /1/. MT= 22 (n,na) cross section Calculated with CCONE code /1/. MT= 24 (n,2na) cross section Calculated with CCONE code /1/. MT= 28 (n,np) cross section Calculated with CCONE code /1/. MT= 32 (n,nd) cross section Calculated with CCONE code /1/. MT= 41 (n,2np) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. The thermal cross section was derived from Shibata/2/. Below 4.01 eV the 1/v cross section was assumed. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /1/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /1/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /1/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /1/. MT=111 (n,2p) cross section Calculated with CCONE code /1/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /1/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /1/. MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 17 (n,3n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 24 (n,2na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) reaction Calculated with CCONE code /1/. MT= 51- 91 (n,n') reaction Calculated with CCONE code /1/. MT=102 Capture reaction Calculated with CCONE code /1/. MT=111 (n,2p) reaction Calculated with CCONE code /1/. MT=600-649 (n,p) reaction Calculated with CCONE code /1/. MT=650-699 (n,d) reaction Calculated with CCONE code /1/. MT=700-749 (n,t) reaction Calculated with CCONE code /1/. MT=750-799 (n,He3) reaction Calculated with CCONE code /1/. MT=800-849 (n,a) reaction Calculated with CCONE code /1/. MF= 8 Information on decay data MT= 4 (n,n') reaction Decay chain is given in the decay data file. MT= 5 Total reaction (except fission) reaction Decay chain is given in the decay data file. MT= 16 (n,2n) reaction Decay chain is given in the decay data file. MT= 17 (n,3n) reaction Decay chain is given in the decay data file. MT= 22 (n,na) reaction Decay chain is given in the decay data file. MT= 24 (n,2na) reaction Decay chain is given in the decay data file. MT= 28 (n,np) reaction Decay chain is given in the decay data file. MT= 32 (n,nd) reaction Decay chain is given in the decay data file. MT= 41 (n,2np) reaction Decay chain is given in the decay data file. MT=102 Capture reaction Decay chain is given in the decay data file. MT=103 (n,p) reaction Decay chain is given in the decay data file. MT=104 (n,d) reaction Decay chain is given in the decay data file. MT=105 (n,t) reaction Decay chain is given in the decay data file. MT=106 (n,He3) reaction Decay chain is given in the decay data file. MT=107 (n,a) reaction Decay chain is given in the decay data file. MT=111 (n,2p) reaction Decay chain is given in the decay data file. MF=10 Nuclide production reactions MT= 4 (n,n') reaction Calculated with CCONE code /1/. MT= 17 (n,3n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT=104 (n,d) reaction Calculated with CCONE code /1/. MT=106 (n,He3) reaction Calculated with CCONE code /1/. MT=111 (n,2p) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./3/ proton : global OMP, A.J.Koning and J.P.Delaroche/4/ deuteron: Y.Han et al./5/ triton : folding OMP, A.J.Koning and J.P.Delaroche/4/ He-3 : Y.Xu et al./6/ alpha : M.Avrigeanu and V.Avrigeanu/7/ * Level scheme of Ce-137 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 + 1 0.160360 1/2 + 2 0.254290 11/2 - 3 0.433970 3/2 + 4 0.514030 3/2 + 5 0.763290 3/2 + 6 0.825780 1/2 + 7 0.836690 5/2 + 8 0.866680 5/2 - 9 0.927700 15/2 - 10 1.104870 3/2 - 11 1.144340 13/2 - 12 1.147200 1/2 - 13 1.179590 5/2 + 14 1.259480 3/2 - 15 1.271370 3/2 + 16 1.288800 5/2 - 17 1.337400 3/2 + 18 1.435390 5/2 + 19 1.476670 3/2 + 20 1.570120 5/2 - 21 1.577200 1/2 + 22 1.602740 3/2 + 23 1.643000 1/2 - 24 1.687100 1/2 - 25 1.693350 1/2 + 26 1.715200 1/2 + 27 1.728100 1/2 - 28 1.800510 1/2 - 29 1.887770 3/2 + 30 1.909000 1/2 - 31 1.925290 3/2 + 32 1.933570 3/2 + 33 1.951690 3/2 + 34 1.980400 15/2 - 35 2.039300 19/2 - 36 2.040600 1/2 - 37 2.061100 1/2 - 38 2.113630 3/2 + 39 2.133660 3/2 + 40 2.142700 1/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/8/) Energy dependent parameters of Mengoni-Nakajima/9/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Ce-138 17.159 2.043 -0.415 0.526 1.385 4.963 3.277 Ce-137 17.591 1.025 0.462 0.434 0.733 2.997 2.275 Ce-136 16.954 2.058 0.739 0.384 2.069 3.374 3.362 Ce-135 16.852 1.033 1.371 0.513 0.089 4.118 1.145 La-137 17.057 1.025 -0.450 0.501 0.579 3.544 2.337 La-136 16.954 0.000 0.209 0.548 -0.975 3.372 1.076 La-135 16.852 1.033 0.811 0.590 -0.514 5.227 1.171 La-134 16.749 0.000 1.312 0.515 -0.932 3.080 0.920 Ba-136 16.940 2.058 -1.401 0.636 0.791 6.443 3.336 Ba-135 16.759 1.033 -0.469 0.568 0.128 4.468 2.075 Ba-134 16.786 2.073 -0.011 0.595 0.763 6.093 3.471 Ba-133 16.836 1.041 0.807 0.552 -0.119 4.590 1.830 Ba-132 16.543 2.089 1.014 0.563 0.841 5.770 3.069 Ba-131 16.286 1.048 1.694 0.586 -0.576 5.200 1.565 --------------------------------------------------------- * Gamma-ray strength functions for Ce-138 E1: hybrid model(GH)/10/ ER= 15.09 (MeV) EG= 4.64 (MeV) SIG= 332.15 (mb) M1: standard lorentzian model(SLO) ER= 7.93 (MeV) EG= 4.00 (MeV) SIG= 0.89 (mb) E2: standard lorentzian model(SLO) ER= 12.19 (MeV) EG= 4.45 (MeV) SIG= 3.26 (mb) References 1) O.Iwamoto, J. 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